Text

Proposed Tech Specs Re Reportable Events,Moderator Temp Coefficient,Fire Detection Instrumentation,Rcs,Eccs & Containment Vessel & Shield Bldg Structural Integrity
	ML20083R331
Person / Time
Site:	Sequoyah
Issue date:	04/20/1984
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20083R310	List: ML20083R307; ML20083R331;
References
	NUDOCS 8404240091
	Download: ML20083R331 (65)
	v • d • e

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ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATIONS SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 6

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QUADRANT POWER TILT RATIO i __

l'.22 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated o'utput to the average of the upper excore detector calibrated outputs, o'r the ratio of the maximum lower excore detector calibrated output to the average of the-lower excore detector calibrated outputs, whichever is greater. With one excore detector inoperable,ithe remaining three detectors shall be used for computing the average. e

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RATED' THER' MAL' POWER

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1.23 RATED THERMAL POWER shall be a total reactor core heat transfer rate to' the Yeactor coolant of 3411 MWt.

s REACTOR TRIP SYSTEM. RESPONSE TIME 1.24 -The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until loss of stationary gripper coil voltage. 3 REPORTABLE Everr 1.25 JA REPORTABLE EVENT shall be any of ttiose conditions specified in section 50.73 to 10 CFR Part 50. ,

SHIELD BUILDING INTEGRITY 1.26 SHIELD BUILDING INTEGRITY shall e'xist when:

a. The door in each access opening is closed except when the a'ccess opening is being Osed for normal transit entry and exit.

b. The emergency gas treatment system.is OPERABLE.

c. The sealing mechanism associated with c.ach penetration (e.g.,

welds, bellows or 0-rings) is OPERABLE.

SHUTDOWN MARGIN

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l.27 SHbTDOWN MARGIN shalf be the instantaneous amount of reactivity by which the reactor is subcritical or.would be subcritical from its present condition assuming all full length rod cluster' assemblies'(shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is' assumed to be fully withdrawn.

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SEQUOYAH - UNIT 1 .1 ,

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a REACTIVITY CONTROL SYSTEMS-MOD'ERATOR TEMPFRATtfor COEFFICIENT

[ s LIMITING CONDITION FOR OPERATION l

i 3.1.1.3 The moderator temperature coefficient (MTC) shall be:

a. Less positive than 0 delta'k/k/*F for the all rods withdrawn, beginning of cycle life (BOL), hot zero THERMAL POWER condition.

! b. Less negative than -4.0 x 10 -4 delta k/k/ F for the all rods with-drawn, end of cycle life (E0L), RATED THERMAL POWER condition.

APPLICABILITY: Specification 3.1.1.3.a - MODES 1 and 2* only#

Specification 3.1.1.3.b - MODES 1, 2 and 3 only#

l ACTION:

l l a. With the MTC more positive than the limit of 3.1.1.3.a above operation in MODES 1 and 2 may proceed provided:

1.

Control rod withdrawal limits are established and maintained sufficient to restore the MTC to less positive than 0 delta' k/k/ F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in HOT STAND 8Y within the next 6 t

l hours. These withdrawal limits shall be.in addition to the insertion limits of Specification 3.1.3.6. -

2.

The control rods are maintained within the withdrawal limits established above until a subsequent calculation verifies that the MTC has been restored to within its limit for the all rods withdrawn condition. ,

3. In lieu of any other report required by Specification 6.6.1, a Special Report is prepared and submitted to the Commission pursuant to Specification 6.9.2 within 10 days, describing the value of the measured MTC, the interim control rod withdrawal limits and the predicted average core burnup necessary for i

restoring the positive MTC to within its limit for the all rods ,

( withdrawn condition. -

! b. With the MTC more negative than the limit of 3 1.1.3.b above, be in il0T SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

^With Kef f greater than or equal to 1.0

See Special Test Exception 3.10.3-SEQUOYAH - UNIT 1 3/4 1-4 /

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INSTRUMENTATION FIRE DETECTION INSTRUMENTATION ,

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LIMITING CONDITION FOR OPERATION 3.3.3.8 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-11 shall be OPERABLE.

APPLICABILITY: Whenever equipment protected by the fire detection instrument is required to be OPERABLE.#

ACTION:

With the number of OPERABLE fire detection instrument (s) less than the minimum number OPERABLE requirement of Table 3.3-11:

a. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the containment, then inspect the containment at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.5.

b. Restore the inoperable instrument (s) to OPERABLE status within 14 days or, in lieu of any other -report required by Specifica-tion 6.6.1, prepare and submit a Special. Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining l the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status,

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.8.1 Each of the above required fire detection instruments which are accessible during operation shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST. Fire detection which are not accessible during plant operation shall be demonstrated OPERABLE ~

by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 6 months.

4.3.3.8.2 The NFPA Code 72D supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months.

4.3.3.8.3 The non-supervised circuits between the local fire protection panels and actuated equipment shall be demonstrated OPERABLE at least once per 6 months.

The fire detection instruments located within the containment are not required-to be OPERABLE during the performance of Type A Containment Leakage Rate Tests. .

SEQUOYAH - UNIT 1 3/4 3-58

r- 1 REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

b. The steam generator shall be determined OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.4-2.

4.4.5.5 Reports

a. Following each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission within 15 days,

b. The complete results of the steam generator tube inservice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following completion of the inspection. This Special Report shall include:

1. Number and extent of tubes inspected.

2. Location and percent of wall-thickness penetration for each indication of an imperfection.

3. Identification of tubes plugged.

c. Results of steam generator tube inspections which fall into Category C-3 . shall De -

reported pursuant to' Specification 6.6.1 prior to resumption of plant operation. The written followup of this report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.

SEQUOYAH - UNIT 1 .3/4 4-10

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STEAM GENERATOtf TUBE INSPECTION E IST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION G ~

Sample Siie Result Action Required Result Action Required Result Action Required A minimum of C-1 None N/A N/A N/A N/A S Tubes per S. G.

C-2 Plug defective tubes C-1 None N/A N/A and inspect additional Plug defective tubes C-1 None 2S tubes in this S. G. C-2 and inspect additional C-2 Plug defective tubes 4S tubes in this S. G.

! Perform action for C-3 C-3 result of first sample

. w Perform action for g , C-3 C-3 result of first N/A N/A sample ,

a C-3 Inspect all tubes in All other

$ this S. G., plug de- S. G.s are None N/A N/A fective tubes and C-1 inspect 2S tubes in Some S. G.s Perform action for each other S. G- N/A N/A C-2 but no C-2 result of second additional sample Prompt notification S. G. are to NRC pursuant C-3 to specification Additional Inspect all tubes in e 6.6.1 S. G. is C-3 each S. G. and plug g defective tubes.

Prompt notification N/A N/A to NRC pursuant to specification 6.6.1 S=3 U % Where N is the number of steam generators in the unit, and n is the number of steam generators inspected during an inspection n.

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REACTOR COOLANT SYSTEM ACTION: (Continued)

MODES 1, 2, 3, 4 and 5

a. With the specific activity of the primary coolant greater than 1.0 microcuries/ gram DOSE EQUIVALENT I-131 or greate" than 100/E microcuries/ gram, perform the sampling and analysis requirements of item 4a of Table 4.4-4 until the specific activity of the nrimary coolant is restored to within its limits. A SPECIAL REPORT shall be prepared and submitted to the Commission pursuant to Specification 6.9.2. within 30 days. This report shall contain the results i

of the specific activity analyses together with the following information:

1. Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded,

2. Fuel burnup by core region,

3. Clean-up flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded,

4. History of de gassing operations, if any, starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded, and

5. The time duration when the specific activity of the primary coolant exceeded 1.0 microcuries/ gram DOSE EQUIVALENT I-131.

SURVEILLANCE REQUIREMENTS 4.4.8 The specific activity of the primary coolant shall be determined to be _

within the limits by performance of the sampling and analysis program of Table 4.4-4.

SEQUOYAH - UNIT 1 3/4 4-20 ,

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EMERGENCY CURE'C00 LING" SYSTEMS TECCS) 3/4.5.2 ECCS SUBSYSTEMS - T,y Greater Than or Equal to 350*F LIMITING CONDITION FOR OPERATION 3.5.2 Two independent ECCS subsystems shall be OPERABLE with each subsystem comprised of:

, a. One OPERABLE centrifugal charging pump, l

b. One OPERABLE safety injection pump,

c. One OPERABLE residual heat removal heat exchanger,

d. One OPERABLE residual heat removal pump, and

e. An OPERABLE flow path capable of taking suction from the refueling water storage tank on a safety injection signal and automatically transferring suction to the containment sump during the recirculation phase of operation.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a. With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a REPORTABLE EVENT shall be prepared and submitted to l

The Commission pursuant to Specification 6.6.1. This report shall include a description of the circumstances fo the actuation and the total accumulated actuation cycles to date. The current value of the _

usage factor for each affected safety injection nozzle shall be provided in'this report whenever its value exceeds o.70.

SURVEILLANCE REOUIREMENTS j 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the following valves are in the indicated positions with power to the valv3 operators removed:

SEQUOYAH - UNIT ~1 3/4'5-5

, , EMERGENCY CORE COOLING SYSTEMS (ECCS)

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3/4. 5.~3 ECCS SlJB$YSTEMS - TavhLessThan350F LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

a. One OPERABLE centrifugal charging pump,

b. One OPERABLE residual heat removal heat exchanger,

c. One OPERABLE residual heat removal pump, and

d. An OPERABLE flow path capable of taking suction from the refueling water storage tank upon being manually realigned and automatically transferring suction to the containment sump during the recirculation phase of operation.

APPLICABILITY: MODE 4.

ACTION:

a. With no ECCS subsystem OPERABLE because of the inoperability of either the centrifugal charging pump or the flow path from the '

refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in COLD SHUT 00WN within-the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

b. With no ECCS subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger cn residual heat removal pump, restore at least one ECCS subsystem to OPERABLE status or maintain the Reactor Coolant System T of alternate heat removal methods. avg less than 350 F by use c.

In the event the ECCS is actuated and injects water into the' Reactor Coolant System, a REPORTABLE EVENT shall be prepared and submitted to The Commission pursuant to Specification 6.6.1. This report shall include a description of the circumstances fo the actuation and the total accumulated actuation cycles to date.

The current value of-the usage in'this factor for each affected safety injection nozzle shall be provided report whenever its value exceeds o.70.

SEQUOYAH - UNIT 1 3/4.5-9

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CONTAi,.mmu araitn3 - ~~~~

CONTAINMENT VESSEL STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION .

3.6.1.6 The structural integrity of the containment vessel shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the structural integrity of the containment vessel not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200 F.

SURVEILLANCE REOUIREMENTS 4.6.1.6 The structural integrity of the containment vessel shall be determined during the shutdown for each Type A containment leakage rate test (Specification 4.6.1.2) by a visual inspection of the exposed accessible interior and exterior surfaces of the vessel. This inspection shall be performed prior to the Type A containment leakage rate test to verify no apparent changes in appearance of the surfaces or other abnormal degradation. Any abnormal degradation of the containment vessel detected during the above required inspections shall be reported to the Commission pursuant to Specification 6.6.1.

4 SEQUOYAH - UNIT l- 3/4 6-11

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SHIELD BUILDING STRUCTURAL INTEGRITY l

LIMITING CONDITION FOR OPERATION ;

! 3.6.1.7 The structural integrity of the shield buildino shall be maintained at a level consistent with the acceptance criteria in Soecification 4.6.l.7. 1 l APPLICABILITY: PODES 1, 2, 3 and 4 I I ACTION:

With the structural integrity of the shield building not conforming to the above reouf rements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200*F.

t SURVEILLANCE REOUIREPENTS 4.6.1.7 The structural integrity of the shield building shall be determined during the shutdown for each Type A containment leakage rate test (reference -

Specification 4.6.1.2) by a visual inspection of the exoosed accessible interior and exterior surfaces of the shield building and verifying no

apparent changes in appearance of the concrete surfaces or other abnormal 4

degradation. Any abnormal degradation of the shield buildino detected during i the above required inspections shall be reported to the Commission pursuant to Specification 6.6,1.

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i SE000YAH - UNIT.1 '3/4 6-12

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PLANT SYSTEMS 3/4.7.11 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.11.1 The fire suppression water system shall be OPERABLE with;

a. Two fire suppression pumps, each with a capacity of 1174 gpm, with their discharge aligned to the fire suppression header,

b. An OPERABLE flow path capable of taking suction from the forebay and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves, the last valve ahead of the water pressure alarm device on each sprinkler or hose standpipe, and the last valve ahead of the deluge valve on each deluge or spray system required to be OPERABLE' per Specifications 3.7.11.2 and 3.7.11.4.

APPLICABILITY: At all times.

ACTION:

a. With only one pump OPERABLE, restore the inoperable equipment to OPERABLE status within 7 days or, in lieu of any other report required by Specification 6.6.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the plans and procedures to be used to restore the inoperable equipment to OPERABLE status or to provide an alternate backup pump or supply. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

b. With the fire suppression water system otherwise inoperable:

1. Establish a backup fire suppression water system within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and

2. In lieu of any other report required by Specification 6.6.1, submit a Special Report in accordance with Specification 6.9.2:

a) By telephone within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b) Confirmed by telegraph, mailgram or facsimile transmission no later than the first working day following the event, and SEQUOYAH - UNIT 1 3/4 7-31

PLANT .

SPRAY AND/0R SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.11.2 The following spray and/or sprinkler systems shall be OPERABLE:

a. Reactor Building - RC pump area, Annulus

b. Auxiliary Building - Elev. 669, 690, 706, 714, 734, 749, 759, ABGTS Filters, EGTS Filters, Cont. Purge filters, and 125V Battery Rooms.

c. Control Building - Elev. 669, Cable Spreading Room, MCR air filters, and operator living area.

d. Diesel Generator Building - Corrider Area.

e. Turbine Building - Control Building Wall.

APPLICABILITY: Whenever equipment protected by the spray / sprinkler system is required to be OPERABLE.

ACTION:

a. With one or more of the above required spray and/or sprinkler systems inoperable, within one hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas establish an hourly fire watch patrol. Restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specifica-tion 6.6.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.11.2 Each of the above required spray and/or sprinkler systems shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path is in its correct position.

b. At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full. travel.

SEQUOYAH - UNIT 1 3/4 7-33

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CO SYSTEMS 2

LIMITING CONDITION FOR OPERATION 3.7.11.3 The following low pressure C0 systems 7

shall be OPERABLE.

a. Computer Room.

b. Auxiliary Instrument Room.

c. Diesel Generator Rooms.

d. Fuel Oil Pump Rooms.

APPLICABILITY: Whenever equipment protected by the CO systems is required to 2

be OPERABLE.

ACTION:

a. With one or more of the above required CO2 systems inoperable, within one hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol. Restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specification

6. 6.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status. -

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.11.3.1 Each of the above required CO systems shall be demonstrated 2

OPERABLE at least once per 31 days by verifying that each valve (manual, power .

operated or automatic) in the flow path is in its correct position.

SEQUOYAH - UNIT 1 3/4 7-35

' PLANT SYSTEMS FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7.11.4 The fire hose stations shown in Table 3.7-5 shall be OPERABLE.

APPLICABILITY: Whenever equipment in the areas protected by the fire hose-stations is required to be OPERABLE.

ACTION:

a. With one or more of the fire hose stations shown in Table 3.7- 5 inoperable, route an additional equivalent capacity fire hose to the unprotected area (s) from an OPERABLE hose station within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if the inoperable fire hose is the primary means of fire suppression; otherwise route the additional hose within 24 iaurs. Restore the fire hose station to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.6.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the station to OPERABLE status.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.7.11.4 Each of the fire hose stations shown in Table 3.7-5 shall be demonstrated OPERABLE:

a. At least once per 31 days by visual inspection of the stations accessible during plant operations to assure all required equipment is at the station,

b. At least once per 18 months by:

1. Visual inspection of the stations not accessible during plant operations to assure all required equipment is at the station,

2. Removing the hose for inspection and re-racking, and

3. Inspecting all gaskets and replacing any degraded gaskets in the couplings,

c. At least once per 3 years by:

1. Partially opening each hose station valve to verify valve OPERABILITY and no flow blockage.

2. Conducting a hose hydrostatic test at a pressure of 150 psig or at least 50 psig above maximum fire main operating pressure, whichever is greater.

SEQUOYAH - UNIT 1 3/4 7-37

PLANT s ..

3/4.7.12 FIRE BARRIER PENETRATIONS LIMITING CONDITION FOR OPERATION l

3.7.12 All fire barrier penetrations (including cable penetration barriers, firedoors and fire dampers) in fire zone boundaries protecting safety related areas shall be functional.

APPLICABILITY: At all times.

ACTION:

a. With one or more of the above required fire barrier penetrations non-functional, within one hour either, establish a continuous fire l watch on at least one side of the affected penetration, or verify i the OPERABILITY of fire detectors on at least one side of the non-l functional fire barrier and establish a hourly fire watch patrol.

Restore the non-functional fire barrier penetration (s) to functional status within 7 days or, in lieu of any other report required by Specification 6.6.1, prepare and submit a Special Report to the

, Commission pursuant to Specification 6.9.2 within the next 30 days l outlining the action taken, the cause of the non-functional pene-tration and plans and schedule for restoring the fire barrier penetration (s) to functional status.

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b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

( SURVEILLANCE REQUIREMENTS l

l l 4.7.12 Each of the above required fire barrier penetrations shall be verified i

i to be functional:

a. At least once per 18 months by a visual inspection

b. Prior to returning a fire barrier penetration to functional status following repairs or maintenance by performance of a visual inspec-tion of the affected fire barrier penetration (s).

SEQUOYA4 - UNIT 1 3/4 7-41

RADI0 ACTIVE EFFLUENTS DOSE

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LIMITING CONDITION FOR OPERATION '

3.11.1.2 The dose or dose commitment to an individual from radioactive materials in liquid effluents released from the site (see Figure 5.1-1) shall be limited to the following*:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and

b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

APPLICA8ILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.6.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose or dose commitment to an individual from these releases is within 3 mrem to the total body and 10 mrem to any organ. This Special Report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act.

b. The provisions of specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11/1.2 Dose Calculatinns. Cumulative dose contributions from liquid effluents shall be determined in accordance with the 00CM at least once per 31 days.

'Perreactoruitit SEQUOYAH - UNIT 1 3/4 11-5

RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be OPERABLE. The appro-priate portions of the system shall 'e cused to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the site (see Figure 5.1-1) when averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mram to any organ

APPLICABILITY: At all times.

ACTION:

a. With the liquid radwaste treatment system inoperable for more than 31 days or with radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Specification 6. 6.1, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action (s) taken to prevent a recurrence.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases shall be projected at least once per 31 days, in accordance with the ODCM.

4.11.1.3.2 The liquid radwaste treatment system shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equipment for at least 15 minutes at least once per 92 days unless the liquid radwaste system has been utilized to process radioact.ive liquid effluents during the previous 92 days.

Per reactor unit SEQUOYAH - UNIT 1 3/4 11-6

RAul0ACiih U fi udie s DOSE - N08t F CARFR e LIMITING CONDITION FOR CPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effic.'nts from the site (see figure 5.1-1) shall be limited to the following*-

a. During any calendar quart er: Less than or equal to b mrad for i,amma radiation and less than or equal to 10 mrad for beto radiatiun and,

b. During any calendar year: less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION a.

With the calculated air dese from radioactive noble gases in gaseous ef fluents exceeding any of the above limits, in lieu of any other report required by Specification 6. 61, prepare and submit to the Com. mission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose is within 10 mrad for gamma radiation and 20 mrad for beta radiation.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the ODCM at least once per 31 days.

3 Per reactor unit.

J SEQ'OYAH - UNIT 1 3/4 11-12

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RADI0 ACTIVE EFFLUENTS DOSE - RADICIODINES. RADIOACTIVE MATERIALS IN PARTICULATE FORM. AND RADIONUCLIDES OTHER THAN NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to an individual from radioiodines and radioactive materials in particulate form, and radionuclides (other than noble gases) with half-lives greater than 8 days in gaseous effluents released from the site (see Figure 5.1-1) shall be limited to the following*:

a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and,

b. During any calendar year: Less than or equal to 15 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radiofodines, radioactive materials in particulate form, or radionuclides (other than noble gases) with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.6.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases of radio-iodines and radioactise materials in particulate form, and radio-nuclides (other than nobles gases) with half-lives greater than 8 days in gaseous effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose or dose commitment to an individual from these releases is within 15 mrem to any organ,

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.11.2.3 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the ODCM at least once per 31 days.

^Per reactor unit.

SEQUOYAH - UNIT 1 3/4 11-13

M RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE. The appropriate portions of the GASEOUS RA0 WASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the site (see Figure 5.1-1), when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation". The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site (see Figure 5.1-1) when averaged over 31 days would exceed 0.3 mrem to any organ."

APPLICABILITY: At all times.

ACTION:

a. With the GASEOUS RADWASTE TREATMENT SYSTEM and/or the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than 31 days or with gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Specifica-tion 6. 6.1, prepare and submit tc the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action (s) taken to prevent a recurrence.

b. The provisirns of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the ODCM.

4.11.2.4.2 The GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREAT-MENT SYSTEM shall be demonstrated OPERABLE by operating the GASEOUS RADWASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 15 minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days.

"These doses are per reactor unit.

SEQUOYAH - UNIT 1 3/4 11-14

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6 RADI0 ACTIVE EFFLUENTS 3/4.11.3 SOLID RADI0 ACTIVE WASTE LIMITING CONDITION FOR OPERATION 3.11.3 The solid radwaste system shall be OPERABLE and used, as applicable in accordance with a PROCESS CONTROL PROGRAM, for the SOLIDIFICATION and packaging of radioactive wastes to ensure meeting the requirements of 10 CFR Part 20 and of 10 CFR Part 71 prior to shipment of radioactive wastes from the site.

APPLICABILITY: At all times.

ACTION:

a. With the packaging requirements of 10 CFR Part 20 and/or 10 CFR Part 71 not satisfied, suspend shipments of defectively packaged solid radioactive wastes from the site.

b. With the solid radwaste system inoperable for more than 31 days, in lieu of any other report required by Specification 6.6.1, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action (s) taken to res+are the inoperable equipment to OPERABLE status,

3. A description of the alternative used for SOLIDIFICATION and packaging of radioactive wastes, and

4. Summary description of action (s) taken to prevent a recurrence.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.11.3.1 The solid radwaste system shall be demonstrated OPERABLE at least once per 92 days by:

a. Operating the solid radwaste system at least once in the previous 92 days in accordance with the PROCESS CONTROL PROGRAM, or

b. Verification of the existence of a valid contract for SOLIDIFICATION to be performed by a contractor in accordance with a PROCESS CONTROL PROGRAM.

SEQUOYAH - UNIT 1 3/4 11-17

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.- RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.4 The dose or dose commitment to any member of the public, due to releases of radioactivity from uranium fuel cycle sources, shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months.

APPLICABILITY: At all times.

ACTION:

a.

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifica-tions 3.ll.l.2.a. 3.11.1.2.b, 3.ll.2.2.a. 3.ll.2.2.b, 3.11.2.3.a. or

3. ll.2.3.b, in lieu of any other report required by Specification 6.6.1, prepare and submit a Special Report to the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding thi limits of Specification 3.11.4. This Special Report shall include an

[*

\.

analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources (including all effluent pathways and direct radiation) for a 12 consecutive month period that includes the release (s) covered by this report. If the estimated dose (s) exceeds the limits of Specification 3.11.4, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and including the specified information of $ 190.ll(b). Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed in other sections of this technical specification.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not appifcable.

SURVEILLANCE REQUIREMENTS 4.11.4 Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shall De determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the 00CM.

v

( SE000YAH - UNIT 1 3/4 11-19 s

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3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

a. With the radiological environmental monitoring program not being conducted as specified in Table 3.12-1, in lieu of any other report required by Specification 6.9.1 or 6.6.2, prepare and submit to commission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence,

b. With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, in lieu of any other report required by Specification 6,9.1 or 6.6.1, prepsre and submit

to the Commission within 30 days from the end of the affected calendar quarter a Report pursuant to Specificiation 6.9.1.13. When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) concentration (2) limit level (1) limit level (2) ...g .0 When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an iidividual is equal to or greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 .

and 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

c. With milk or fresh leafy vegetable samples unavailable from one or -

more of the sample locations required by Table 3.12-1, in lieu of any other report required by Specification 6.9.1 or 6.6.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause of the unavai'c illity of samples and identifies locations for obtaining replacemer samples.

The locations from which samples were unavailable may then be deleted from those required by Table 3.12-1, provided the locations from which the replacement samples were obtained are added to the environmental monitoring program as replacement locations.

d. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

A special report pursuant to Specification 6.9.2.

SEQUOYAH - UNIT 1 3/4 12-1

RADIOLOGICAL ENVIRONMENTAL MONITORING 3 /4 '.

LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden" of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles. (for elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify the locations of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles.)

APPLICABILITY: At all times.

ACTION:

a. With a land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the maximum values currently being calculated in Specification 4.11.2.3.1, in lieu of any other report required by Specification 6.6.1., prepare and submit to the Commission within 30 days after the updated calculation, pursuant to Specification 6.9.2, a Special Report which identifies the new location (s),

b. With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than the highest calculated dose or dose commit-ment at a location from which samples are currently being obtained in accordance with Specification 3.17.1, in lieu of any other report require by Specification 6. 6.1, prepare and submit to the Commission within 30 days after the updated calculation, pursuant to Specification 6.9.2, a Special Report which identifies the new location. The new location shall be added to the radiological environmental monitoring program within 30 days, if the owner consents. The sampling location, excluding the control station location, having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring Lrogram af ter October 31 of the year in which this land use census was conducted.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted at least once per calendar year between the dates of April 1 and October I using the following techniques:

1. Within a 2-mile radius from the plant or within the 15-mrem / year isodose line, whichever is larger, enumeration by a door-to-door or equivalent counting technique.

2. Within a 5-mile radius from the plant, enumeration by using appropriate techniques such as door-to-door survey, mail survey, telephone survey, aerial survey, or information from local agricultural authorities or other reliable sources.

Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the bl0 hest 0/Q in lieu of the garden census.

SEQUOYAH - UNIT 1 3/4 12-10

AD!-

d. Review of proposed changes to the Technical Specifications related to radiological assessments involving dose calculations and projections and environmental monitoring.

Authority

6. 5. 3. 7 The RARC shaII:

a. Recommend in writing to the Chief, Radiological Hygiene Branch approval or disapproval of items considered under 6.5.3.6 above,

b. Render determinations in writing with regard to whether or not each item considered under 6.5.3.6 constitutes an unreviewed safety question.

c. Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Director, Nuclear Power Division and the Nuclear Safety Review Board of disagreement between the RARC and the Chief, Radiological Hygiene Granch; however, the Chief, Radiological Hygiene Branch shall have responsibility for resolution of such disagreement pursuant to 6.1.2 above.

Records 6.5.3.8 The RARC shall maintain written minute's of each RARC meeting that at a minimum, document the results of all RARC activities performed under the responsibility and authority provisions of these technical specifications.

Copies shall be provided to the Director, Nuclear Power Olvision, PORC, and the Nuclear Safety Review Board.

6. 6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENT!

a. The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.

Each REPORTABLE EVENT shall be reviewed by the PORC and the results of this review shall be submitted to the NSRB and the Director, Nuclear Power Division.

6. 7 SAFETY LIMIT V!OLATION

6. 7.1 violated:

The following actions shall be taken in the event a Safety Limit is

a. The unit shall be placed in at least HOT STANOBY within one hour.

b. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Director, Nuclear Power Division and the NSRB shall be notified with 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SEQUOYAtt - UNIT 1 6-14

. AftMINISTRATIVF CONfROLS ._ _ ___

6. 9 REPORilNG REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Of fice of Inspection and Enforcement unless otherwise noted.

STARTUP REPORT 6.9.1.1 A sumary report of plant startup and power escalat ion te' t ing shall be submitted following (1) teceipt of an operating licen'e, (2) amenriment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nucirir, thermal, or hydraulic perfnrmance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisf actory operation ', hall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

6. 9.1. 3 Startup reports shall be submitted within (1) 90 days f olinwing completion of the startup test program, (2) 90 days followinq resumption or comencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e. , initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), sunplementary reports shall be submitted at least every three months until all three events have been completed.

5[QUOYAH - UNIT 1 6-16

ADM!NisTRATivr enNTRnt9 The radioactive of fluent release report to be submitted 60 days af ter January 1 of each year shall also include an assessment of radiation doses to the likely most e.xposed members of the public from reactor releases and other nearby uransuri funi cycle sources (including doses from primary effluent pathways and direta radiation) for the previous 12 consecutivo months to show conformance with 40 CfA A'), Environmental Radiation Protection Standards for Nuclear Power Operation. Accept.nla toetrods for calculating the dose contribution f rom liquid and gasemis of t iagn+.s are given in Regulatory Guide 1.109. Rev.1.

Thu rar6oactive ef fluent rol6se r= ports shall include the following information for eacn type of solid wau wilpoed of fsite during the report period:

a. Conto nor volume,'

s/

l , b. Total cc ie quantity (specify wNtt'icr determined by measurement or estimate),

c. Prf*.ctrilradionucl' des (specirpwhetherdoterminedbymeasurement or estimate),

d Type o f w gste (e.g. , spent retite, co pacted dry was'.o evaporator bottoms), ,

I. Type of container (e.g. , LSP, 'jpo. A, type 0, Large Quantity), and 1

f. 50L10!FICATION agent (e.g. , coment, ures formaldehyde).

The radioactive affluttnt release #,rports shall e,clude unplanned roleases frcm i

l the site to unrestricted areas'Jr.radioactivM materials in qasenus and liquhl

tfluents on a quar *.orly Danis.

l l The radia* tive ef fluent releno reports shall include any changes to the N# TIS $ CONTROL PROGWAM (Pf.P) Add itving the repe rting period.

MdNTHil,2J At. r:A OPf RA!!T, grpeg '

C.9.1.10 htine reports of vf,srattra ststirtles and shutdown experience, i.mluding occuteentation of all challenges to the PORVs or Safety Valves, shall be sub-itted on a monthly basis to the Dirtr. tor, Of fice of Management and Woqram Analysis, U.S. Nuclear Regulatory Cototilssion Washington, D.C. 20555, with a copy to the Reg hnal Office of Inspectan and Enforcement, no later il Jn t'e 15th of each v'anth following the calendar month covered by the report.

Any changas to the OtTS!TE 005C CALCULATION MA #t'AL shall be submitted with the Mo"thly therating Re pert within 90 days in wntrh the change (s) was mado ef fective, in addition, a rep'rt 3f Any majof Chate,en to the radioactive waste treatment systemt shall be ,; Wtied with the Monthly Operating Report for the period in

' .nich the avsluatten 44s reviewed and accepted by the PORC.

f StQUOYAH Lntf 1 6-19 y $ 8 e

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SEQUOYAH H, UNIT 1- 21 I

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ADMINISTRATIVE CONTROLS RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.14 The W(z) function for normal operation shall be provided to the Direc-tor, Nuclear Reactor Regulation, Attention, Chief of the Core Performance Branch, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555 at least 60 days prior to cycle initial criticality. In the event that these values would be submitted at some other time during core life, it will be submitted 60 days prior to the date the values would become effective unless otherwise exempted by the Commission.

Any information needed to suport W(z) will be by request from the NRC and need not be included in this report.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified for each report.

6.10 RECORD RETENTION In addition to the applicable record retention requirements of_ Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.1 The following records shall be retained for at least five years:

a. Records and logs of unit operation covering time interval at each power level .

b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

c. All REPORTABLE EVENTS submitted to the Commission.

d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications. l

e. Records of changes made to the procedures required by Specification i 6.8.i and 6.8.4.

f. Records of radioactive shipments. l

g. Records of sealed source and fission detector leak tests and results.

~

h. Records of annual physical inventory of all sealed source material j

-of record.

SEQUOYAH - UNIT 1 6-22

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! REACTOR COOLANT SYSTEM l

i BASES-I The plant is expected to be operated in a manner such that'the secondary coolant will be maintained within those chemistry limits found to result in negligible corrosion of the steam generator tubes. If the secondary coolant chemistry is not maintained within these limits, localized corrosion may

, likely result in stress corrosion cracking. The extent of cracking during plant operation would be limited by the limitation of steam generator tube leakage between the primary coolant system and the secondt y coolant system (primary-to-secondary leakage = 500 gallons per day per steam generator).

] Cracks having a primary-to-secondary leakage less than this limit during j operation will have an adequate margin of safety to withstand.the loads imposed j during normal operation and by postulated accidents. Operating plants have demonstrated that primary-to-secondary leakage of 500 gallons per day per steam generator can readily be detected by radiation monitors of steam generator blowdown. Leakage in excess of this limit will require plant shutdown and an l- unscheduled inspection, during which the leaking tubes.will be located'and q plugged.

d i~

Wastage-type defects are unlikely with proper chemistry treatment of the secondary coolant. However, even if a defect should develop in service, _it will be found during scheduled inservice steam generator tube examinations.

! Plugging will be required for all tubes with imperfections exceeding the 1

plugging limit of 40% of the tube nominal wall thickness. Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the original tube wall thickness.

~ Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be promptly reported to the:

Commission pursuant to Specification 6.6.1 prior to resumption of plant opera-

tion. Such ca3es will be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations,' tests,1 additional eddy-current inspection, and revision of the. Technical Specifications,-

l if necessary. -

3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE' l

.. 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS 1

The RCS leakage detection systems required by this-specification are providedlto monitor and-detect leakage from the. Reactor Coolant Pressure.

Boundary. These detection-systems are consistent with the recommendations ofi

. Regulatory Guide 1.45, " Reactor. Coolant Pressure' Boundary. Leakage. Detection J . Systems," May.1973.-

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cSEQUOYAHl-. UNIT'1 . B 3/4 4-3: 7-

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DEFINITIONS PURGE - PURGING 1.21 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure,-humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

QUADRANT POWER TILT RATIO ..

1.22 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore-detector calibrated output to the average.of the upper excore detector cali-brated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, which-ever is greater. Witn one excore detector inoperable, the-remaining three detectors shall be used for computing the average.

, RATED THERi'AL PCWER 1.23 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reacter coolant of 3J11 MWt.

REACTOR TRIP SYSTEM RESPCNSE TIME 1.24 The REACTOR TRIP SYSTEM RESPCNSE TIME snall be the time interval. from when the monitored parameter exceeds its trip setpoint at the channel sensor until loss of stationary gripper coil voltage.

REPORTABLE EVENT 1.25 A REPORTABLE EVENT shall be any of those conditions specified in

lSection 50.73 to lo CFR Part 50.

SHIELO EUILDING INTEGRIT't 1.26 SHIELD BUILDING INTEGRITY shall exist when:

a. -The door in each access opening is closed except'wnen the access.

opening is being useo for normal transit entry and: exit,

b. The emergency gas treatment system is OPERABLE.

c. The sealing mechanism associated with each penetration (e.g. , welds,~'

bellows or 0-rings)lis OPERABLE. '

SEQUOYAH - UNIT-2 ' .1- 5 i

l f REACTIVITY CONTROL ~ SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CCNDITICN FOR OPERATION 3.1.1.3 The moderator temperature coefficient (MTC) shall be:

a. Less positive than 0 delta k/4/*F for the all rods withdrawn, 4 beginning of cycle life (80L), hot zero THERMAL POWER condition.

l b. Less negative than.-4 x 10'4 delta k/k/'F for.the all rods withdrawn .

end of cycle life (EOL), RATED THERMAL POWER condition.

i APPLICABILITY: Specification 3.1.1.3.a - MODES 1 and 2* only#

Specification 3.1.1.3.b - MODES 1, 2 and 3 only#

ACTION:

a. With the MTC more positive than the limit of 3.1.1.3;a above, operation in MODES 1 and 2 may proceed provided:

1. Control rod withdrawal limits are establisned and maintained sufficient to restore the MTC to less positive than 0 delta k/k/ F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in HOT STANDBY within thernext^

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . These withdrawal limits shall be in addition to the-insertion limits of Specification 3.1.3.6.

2. The control rods are maintained within the withdrawal-limits' .

established above until a subsequent calculation verifies.that.

the MTC has been restored to within its; limit for the all rods withdrawn condition.

3. In 1.ieu of any other report . required by Specification 6.6.1, a Special Report is prepared and submitted to the; Commission pursuant to Specification 6.9.2 within 10 days, describing .the value of the measu'ed r MTC, the interim control rod withdrasal limits and the predicted average' core burnup necessary:for.

restoring the ' positive MTC' to within its -limit for the all rods'

, withdrawn condition. +

t

. b. -With the MTC more negative th'an the limit of 3.1.1'3.b above, be in-

~

HOT SHUTDOWN within.12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

"Witn K,ff greater than or equal-t'o 1.0 ~

See Special Test Exception 3.10.3 -

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' SEQUOYAH:- UNIT 12, .3/4 1 ~

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INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITICN FOR OPERATION 3.3.3.3 As a minimum, the fire detection instrumentation for each fire detection zone shcwn in Table 3.3-11 shall be OPERABLE.

APPLICABILITY: Whenever equipment protected by the fire detection instrument is requirec tc ce OPERABLE.#

ACTION:

With the number of OPERABLE fire detection instrument (s) less than the minimum number GPERABLE recuirement of Table 3.3-11:

a. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire' watch patrol to inspect the zone (s) with the incperable instrument (s) at least once per hour, unless the instrument (s) is located inside the containment, then inspect _the containment at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the containment air temperature at least once oer hour at the locations listed in Sceci fication 2.6.1.5.

b. Restere the inoperabie instrument (s) to OPERABLE status witnin 14 aays or, in lieu of any other report required by Specifica-tion 6.6.1, prepare and submit a Special Report to the. Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inocerability anc the plans and schecule- for restoring tne instrument (s) to OPERABLE status.

c. The provisions of Specifications 3.0.3 and 3.0.4 are _not acpiicaole.

5L'RVEILLANCE RECUIREENTS

-4.3.3.S.1 Eacn of the above required fire detection instruments wnich are accessible during operation shall be demonstrated OPERABLE at least once oer 6 months by performance of a CHANNEL FUNCTIONAL' TEST. Fire detection which-are not accessible during plant operation shall tue demcnstrate'd CPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during eacn COLD SHUTOGbN exceeding 24. hours u.11ess performed in the previous 6 months.

4.3.3.8.2 The NFPA Stancard'72D supervised circuits supervision associated with the. detector alarms of eacn of the above. required fire detection instru-ments shall be demonstrated OPERABLE at least once per 6 months.

a.3.3.9.3 The non-supervisec circuits between the local fire protection-panels and' actuated equipment snallLbe demonstrated OPERABLE at.least once per-6 months.

'#The fire detection instruments located within the containment are not cequired

. to be OPERABLE during the performance of Type A Containment Leakage Rste -Tests.

SEQUOYAH --UNIT 2 3/4-3-59 j

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

9. Preservice Insoection means an inspection of the full length of each tube in eacn steam generator performed by edoy current techniques prior to service to establish a baseline condition of the tubing. This inspection shall be performea prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.

b. The steam generator shall be determined OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing througn-wall cracks) required by Table 4.4-2.

4.4.5.5 Reoorts

a. Following each inservice inspection of steam generator tubes,.the number of tubes plugged in each steam generator shall be reported to the Commission within 15 days.

i b. The complete results of the . steam generator tube inservice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of.the inspection. This Special Report shall include:

1. Number and extent'of tubes inspected.

2. Location and percent of wall-thickness penetration forJeach indication of an~ imperfection.

3. Identification of tubes plugged.

.c. Results of' steam generator tube inspections which fall' into Category --

C-3 shall be reported pursuant to Specification"6.6.1 prior. to resumption.of-

, plant operation. The written followup of this report shall provide a description of investigations conducted to determine cause of.the-

-tube degradation and corrective measures taken'to praver.t recurrence.

i 1

SECUOYAH - UNIT 2 '3/4 4-14

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.- - .i% _ m _,.J

' TAllLE 4.4-2 E

8 2

x STEAM GENEftATOft tulle INSPECTION e

2ND SAMPLE INSPECTION 3HD SAMPLE INSPLCTION E IST SAMPLE INSPECTION Actiore licquired flesoll Action iterruised Insult Action lleituncil H Sample Size Itchult tu N/A C-1 None N/A N/A N/A A minimum of S Tut,es per S. G. N/A C -- 2 Plug defective tubes C- 1 None N/A aeul ni:,pect ailihtuni. Plou detective tuises C1 None 2S tubus nitins S. G. C2 .nul inslu i.t .ulihtional C- 2 Plug defective toises 4S solics in ilus S. G.

Pesform action for C-3 C--3 result of first sample Perform action for w C-3 C--3 sesult of fust N/A N/A g Sanipte i C-3 Inspect all tutms in Allothes None N/A N/A g this S. G.. plu9 de S. G 6 are C-1 fective tubes and inst.ei.t 2S tubes in Some S. G.s Perfuim action for N/A N/A cach other S. G. C-2 but no C - 2 schult of second addi tionJ1 gggplg Prompt notification S. G. are to NRC purso.snt C3 to Niccification Additional Inspect all tubes in 6.6.1 S. G. is C--3 each S. G. and plug defective tubes.

Piompt notification N/A N/A to NHC pursuant to speuticatiori 6.6.1 Where N es the numtwr of stearn generators in the unit. and n is the nuinber of steam generators inspected S=3 % during an inspe tion n

REACTOR COOLANT SYSTEM ACTION: (Continued)

1CCES 1, 2, 3, 4 and 5:

a. 'dith the specific activity of the primary coolant greater than 1.0 _ microcurie per gram DOSE EQUIVALENT I-131 or greater than 100/E microcuries per gram, perform the samoling and analysis requirements of item da of Table 4.4-4 until the specific activity of the primary coolant is restored to within its limits. A SPECIAL REPORT shall be prepared and submitted to the Commission pursuant ta Specification 6.9.2 within 30 days. This report shall contain the results of the specific activity analyses together with the following information:

1. Reactor ocwer history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first samole in which the limit was exceeced,

2. cuel burnup cy core region,

3. Clean-up f!cw history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to tne first sample in which the limit was exceeded, 4 History of de gassing cperations, if any, starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded, and

5. The time cerition when tne specific activity of the primary coolant exceeded 1.0 microcurie per gram DOSE EQUIVALENT I-131.

SURVEILLANCE REOUIREMENTS 4.4.8 The specific activity of the primary-coolant-shall be determined to be within the limits by performance of, the sampling and ' analysis program of

. Table ~4.4-4 l

1 SEQUOYAH - UNIT 2 3/4 4-25. ,

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l

l i

EMERGENCY CORE ' COOLING SYSTEMS '(ECCS'f ~ -'"~~' ~ ~~~ '""~'"'

3/4.5.2 ECCS SUBSYSTEMS - T,y Greater Than or Eoual to 350*F LIMITING CONDITION FOR OPERATION 3.5.2 comprisedTwo independent of: ECCS subsystems shall be OPERABLE with each subsystem

a. One OPERABLE centrifugal charging pump,

b. One OPERABLE safety injection pump, c.

One OPERABLE residual heat removal heat exchanger,

d. One OPERABLE residual heat removal pump, and e.

An OPERABLE flow path capable of taking suction from the refueling water storage tank on a safety injection signal and automatically.

transferring phase suction to the containment sump during the recirculation of operation.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a.

With one ECCS subsystem inoperable, restore the inoperable subsystem to GPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within hours, the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6

b. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a REPORTABLE EVENT shall be prepared and submitted to The Commission pursuant to Specification 6.6.1. This report shall include a description of the circumstances fo the actuation and the-total accumulated actuation cycles to date. Tine current value of the usage factor for each affected safety injection nozzle shall be provided in' this report.whenever its value exceeds o.70.

SURVEILLANCE REOUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:

a.

At -least once per 1;2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months by verifying that the following valves are in the indicated positions with power to the valve. operators removed:

SEQUOYAH -' UNIT 2- 3/4 5-5

l EMERGENCY CORE COOLING SYSTEMS 3/4.5.3 ECCS SUBSYSTEMS - T LESS THAN 350 F avg LIMITI'lG CONDITION FOR OPERATICN 3.5.3 As a minimum, one ECCS suosystem comprised of the following shall be OPERABLE:

a. One CPERABLE centrifugal charging pump,

b. One OPERABLE residual heat removal heat exchanger,

c. One OPERABLE residual heat removal pump, and

d. An OPERABLE flow path capable of taking suction from the refueling water storage tank upon being manually realigned and automatically transferring. suction to the containment sump during the recirculation pnase of cperation.

APPLICABILITY: MODE 4.

ACTION:

a. With no ECCS subsystem GPERABLE because of the inoperability of either the centrifugal charging pumo or the ficw path from.the.

refueling water storage tank, restore at least one-ECCS subsystem to OPERABLE status within I hour or be in COLD SHUTCOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months . .

5. With no ECCS suosystem GPERABLE because of the inocersoility of-either the residual heat removal heat exchanger or residual heat removal pump, restore at least one.ECCS subsystem _to OPERABLE status or maintain the Reactor Coolant System T 1ess than 350 F by use-avg of alternate heat removal methods.

0-~ In the event the ECCS is actuated 'and injects water'into the Reactor Coolant System, 'a REPORTABLE EVENT shall be prepared and submitted to The Commission pursuant to Specification 6.6.1. This report shall' include a description of the circumstances fo the actuation and the total accumulated actuation cycles to date. Tite current.value_of.the ,

usage factor for_ each affected safety injection nozzle shall be.provided in'this. report whenever its value exceeds 0.70.~

SEQUOYAH - UNIT 2 - 3/4 5-9:'

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1

a CONTAINMENT SYSTEMS CONTAINMENT VESSEL STRUCTURAL INTEGRITY LIMITING CCNDITIC4N FOR OPERATION l

3.6.1.6 The structural integrity of the containment vessel shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.

APPLICABILITY: MODES 1, 2, 3 and 4. ,

i ACTICN:

With the structural integrity of the containment vessel not conforming to the above requirements, restore.the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200 F.

SURVEILLANCE RECUIREMENTS 4.6.1.5 The structural integrity of the containment vessel shall be determined during the shutdown for each Type A containment leakage rate test (reference' Specification a.6.1.2) by a visual inspection of the exoosed accessible interior and exterior surfaces of the vessel. This inspection shall be performed prior to the Type A containment leakage rate test to verify no apparent changes in 3ccescance of the surfaces or other abnormal degradation. Any abnormal degra-cation of the containment vessel detected during the acove requireo inspec-tions shall be reported to the Commission pursuant to Specification 6.6.l.

.,c .. .

SEQUOYAH - UNITL2 73/4 6 ,

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CONTAINMENT SYSTEMS SHIELO BUILDING STRUCTURAL INTEGRITY LIMITING CCNDITION FOR OPERAT!0N

.3.6.1.7 The structural integrity of the shield building shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.7. '

APPLICABILITY: MODES 1, 2, 3 and 4 ACTION:

With the structural integrity of the shield building not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200 F.

SURVEILLANCE MEOUIRE.MENTS i 4.6.1.7 The structural integrity of the shield building shall be determined during the snutdown for each Type A containment leakage rate test (reference Specification 4.6. i.2) oy a -visual inspection of the exposea accessible interior and exterior surfaces of the snield building and verifying no apparent changes in appearance of .the concrete surfaces or other abnormal degradation. Any abnormal degradation of tne shield building detected during the above required '

inspec-ions shall be reported to the Commission pursuant to Specification.

6.6.1.

i i

SEQUOYAH - UNIT 2 3/4 6-12. !

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PLANT SYSTEMS 3/4.7.11 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.11.1 The fire suppression water system shall be OPERABLE with:

a. Two fire suppression pumps, each with a capacity of 1174 gpm, with their discharge aligned to the fire suppression header, and

b. An OPERABLE flow path capable of taking suction from the forebay and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves, the last valse ahead of the water pressure alarm device on each sprinkler or hose standpipe, and the last valve ahead of the deluge valve on each deluge or spray system required to be OPERABLE per Specifications 3.7.11.2 and 3.7.11.4.

APPLICABILITY: At all times.

ACTION:

a. With only one pump OPERABLE restore the inoperable equipment to OPERABLE status within 7 days or, in lieu of any other report required by Specification 6.6.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the plans and procedures to be used to restore the inoperable equipment to OPERABLE status or to provide an alternate backup pump or supply. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

b. With the fire suppression water system otherwise inoperable:

~

1. Estab1ish a backup fire suppression water system within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and

2. In lieu of any other report required by Specification 6.6.1, submit a Special Report in accordance with Specification 6.9.2:

a) By telephone within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b) Confirmed by telegraph, mailgram or facsimile transmission

- no later than the first working day following the event, and J

SEQUOYAH - UNIT 2 3/4 7-43 eWW

r PLANT SYSTEMS SPRAY AND/OR SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.11.2 The following spray and/or sprinkler systems shall be OPERABLE:

a. Reactor Building - RC pump area, Annulus

b. Auxiliary Building - Elev. 669, 690, 706, 714, 734, 749, 759, ABGTS Filters, EGTS Filters, Cont. Purge Filters, and 125V Battery Rooms.

c. Control Building -

Elev. 669, Cable Spread'ing Room, MCR air filters, and operator living area.

d. Diesel Generator Building - Corricor Area.

e. Turbine Building - Control Building Wall.

APPLICABILITY: Whenever equipment protected by the spray / sprinkler system is requirea to ce OPERABLE.

ACTION:

a. With cne or more of the above required spray and/or sprinkler systems inoperable, within one hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas establish an hourly fire watch patrol. Restore the system to OPERABLE status within 14 days or, in lieu of any other repnrt required by Specifica-tion 6.6.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of th'e inoperability and the plans and

~

schedule for restoring the system to OPERABLE status.

b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.7.11.2 Each of the above required spray and/or sprinkler systems shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path is in. Its correct position.

b. At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel.

SEQUOYAH - UNIT 2 3/4 7-45

PLANT SYSTEMS --

CO SYSTEMS 2

LIMITING CONDITION FOR OPERATION 3.7.11.3 The following low pressure CO systems shall be OPERABLE.

2

a. Computer Room

b. Auxiliary Instrument Room

c. Diesel Generator Rooms

d. Fuel Oil Pump Rooms APPLICABILITY: Whenever equipment protected by the CO systems is required to be OPERABLE. 2 ACTION:

a. With one or more of the above required CO2 systems inoperable, within one hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol. Restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.6.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVtILLANCE REOUIREMENTS 4.7.11.3.1 Each of the above required CO systems shall be demonstrated OPERABLE at least once per 31 days by ver,Tfying that each valve (manual, power operated or automatic) in the flow. path is in its correct position.

4.7.11.3.2 Each of the above required low pressure CO systems shall be demonstrated OPERABLE: 2

a. At least once per 7 days by verifying the C07 storage tank level to be greater than 50% and pressure to be greater than 270 psig, and

b. At least once per 18 months by verifying:

1. The system valves and associated ventilation di..npers and fire door release mechanisms actuate manually and automatically, upon receipt of a simulated actuation signal, and

2. Flow from each nozzle during a " Puff Test."

SEQUOYAH - UNIT 2 3/4 7-47 a4*e

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l'LANT SYSTEMS FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7.11.4 The fire hose stations shown in Table 3.7-5 shall be OPERABLE.

APPLICABILITY: Whenever equipment in the areas protected by the fire hose stations is required to be OPERABLE.

ACTION: .

a. With one or more of the fire hose stations shown in Table 3.7-5 inoperable, route an additional equivalent capacity fire hose to the unprotected area (s) from an OPERABLE hose station within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if tho inoperable fire hose is the primary means of fire suppression; other-wise, route the additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Restore the fire hose station to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.6.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability, and plans and schedule for restoring the station to OPERABLE status.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.11.4 Each of the fire hose stations shown in Table 3.7-5 shall be demonstrated OPERABLE:

a. At least once per 31 days by a visual inspection of the fire hose stations accessible during plant operations to assure all required equipment is at the station.

b. At least once per 13 months by:

1. Visual inspection of all the stations not accessible during plant operations to assure all required equipment is at the station.

2. Removing the hose for inspection 'and re-racking, and

3. Inspecting all gaskets and replacing any degraded gaskets in the couplings.

c. At least once per 3 years by:

1. Partially opening each hose station valve to verify valve OPERABILITY and no flow blockage.

2. . Conducting a hose hydrostatic test at a pressure of 300 psig or at least 50 psig above maximum fire main operating pressure, whichever is greater.

SEQUOYAH - UNIT 2 3 /47-48

PLANT SYSTEMS 3/4.7.12 FIRE BARRIER PENETRATIONS LIMITING CONDITION FOR OPERATION 3.7.12 All fire barrier penetrations (including cable penetration barriers, firedoors and fire dampers) in fire. zone boundaries protecting safety related areas, shall be functional.

APPLICABILITY: At all times.

ACTION:

a. With one or more of the above required fire barrier penetrations non-functional, within one hour either, establish a continuous fire watch on at least one side of the affected penetration, or verify the OPERABILITY of fire detectors on at least one side of the non-functional fire barrier and establish a hourly fire watch patrol.

Restore the non-functional fire barrier penetration (s) to functional status within 7 days or, in lieu of any other report required by Specification 6.6.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the non-functional pene-tration and plans and schedule for restoring the fire barrier penetration (s) to functional status.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.7.12 Each of the above required fire barrier penetrations shall be verified to be functional: , . .

a. At least once per 18 months by a visual inspection,

b. Prior to returning a fire barrier penetration to functional status following repairs or maintenance by performance of a visual inspection of the affected fire barrier penetration (s).

SEQUOYAH - UNIT 2 3/4 7-52

n-i t

RADI0 ACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or. dose' commitment to an individual from radioactive materials in liquid effluents released from the site (see Figure 5.1-1) shall be limited to the following*:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and

b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

' APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the' release of radioactive materials in liquid effluents exceeding any of the'above limits, in lieu of ,

any other report . required by Specification &6.1, prepare and submit . l to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective. actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose or dose commitment to an individual from these releases is within 3 mrem to the total body and 10 mrem to any organ. This Special Report shall also include (1) the results of radiological analyses of the' drinking water source and (2)'the radiological impact on finished drinking :

water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act.

b. The provisions of specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Dose Calculations. Cumulative' dose contributions from liquid effluents shall be determined in accordance with the 00CM at least once per 31 days;

~

"Per reactor unit SEQUOYAH - UNIT 2 3/4 11-5

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RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT-LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be OPERABLE. The appro-priate portions of the system shall be used to reduce the. radioactive materials

'in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the site (see Figure 5.1-1) when averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ .a APPLICABILITY: At all times.

ACTION:

With the liquid radwaste treatment system inoperable for more than

~

a.

31 days or with radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Specificatica G.6.1, prepare and submit to the Commission within 30 days pursuant to Specification'6.9.2 a Special Report which includes the following information:

1. Ids an of the inoperable equipment or subsystems and t'. , lor inoperability,.

2. Ac'. son (s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action (s) taken to prevent a recurrence.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIR5MENTS 4.11.1.3.1 Doses due to liquid releases shall be projected atLleast once per 31 days, in accordance with the ODCM.

4.11.1.3.2 The liquid radwaste treatment system shall be ' emonstrated d OPERABLE by operating the liquid radwaste treatment system equipment for at least-15 minutes at least once per 92 days unless.the liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days.

"Per reactor unit.

SEQUOYAH - UNIT 2 -3/4 11-6 a

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RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents from the site (see Figure 5.1-1) shall be li,mited to the following*:

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and,

b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.6.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose is within 10 mrad for gamraa radiation and 20 mrad for beta radiation.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

~

SURVEILLANCE REQUIREMENTS .

4.11.2.2 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the 00CM at least once per.31 days.

"Per reactor unit.

SEQUOYAH - UNIT 2 3/4 11-12

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l RADI0 ACTIVE EFFLUENTS DOSE - RADI0 IODINES, RADIOACTIVE MATERIALS IN PARTICULATE FORM, AND RADIONUCLICES OTHER THAN NOBLE GASES l

LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to an individual from radiofodines and radioactive materials in particulate form, and radionuclides (other than noble gases) with half-lives greater than 8 days in gaseous effluents released from the site (see Figure 5.1-1) shall be limited to the following*:

a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and,

b. During any calendar year: Less than or equal to 15 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radiciodines. radioactive materials in particulate form, or radionuclides (other than noble gases) with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.6.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases of radio-iodines and radioactive materials in particulate form, and radio-nuclides (other than nobles gases) with half-lives greater than 8 days in gaseous effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose or dose commitment to an individual from these releases is within 15 mrem to any organ.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the ODCM at least once per 31 days.

Per reactor uni t.

SEQUOYAH - UNIT 2 3/4 11-13 j

e RADI0 ACTIVE EFFLUENTS GASEOUS RA0 WASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE. The appropriate portions of the GASEOUS RADWASTE TREATMENT SYSTEM shall be used. to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the site (see Figure 5.1-1), when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation". The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site (see Figure 5.1-1) when averaged over 31 days would exceed 0.3 mrem to any organ.*

APPLICABILITY: At all times.

ACTION:

a. With the GASEOUS RADWASTE TREATMENT SYSTEM and/or the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than 31 days or with gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Specifica-tion 6. 6.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report whicn includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action (s) taken to prevent a recurrence.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the 00CM.

4.11.2.4.2 The GASEOUS RA0 WASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREAT-MENT SYSTEM shall be demonstrated OPERABLE by operating the GASEOUS RA0 WASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 15 minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days.

^These doses are per reactor unit. -

SEQUOYAH - UNIT 2 3/4 11-14

I RADIOACTIVE EFFLUENTS 3/4.11.3 SOLID RADIOACTIVE WASTE LIMITING CONDITION FOR OPERATION 3.11.3 The solid radwaste system shall be OPERABLE and used, as applicable in accordance with a PROCESS CONTROL PROGRAM, for the SOLIDIFICATION and packaging the requirements of 10 CFR Part 20 and of of radioactive 10 CFR Partwastes 71 priorto ensure meeting' to shipment of radioactive wastes from the site.

APPLICABILITY: At all times.

ACTION:

a. With the packaging requirements of 10 CFR Part 20 and/or 10 CFR Part 71 not satisfied, susoend shipments of defectively packaged solid radioactive wastes from the site.

b. With the solid radwaste system inoperable for more than 31 days, in lieu of any other report required by Specification 6.6.1, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report which- includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action (s) taken to restore the inoperable equipment to OPERABLE status,

3. A description of the alternative used for SOLIDIFICATION and packaging of radioactive wastes, and

4. Summary description of action (s) taken to prevent a "ecurrence.

c. The provis~ ions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.3.1 The solid radwaste system shall be demonstrateo OPERABLE at least once per 92 days by:

a. Operating the solid radwaste system at least once in the previous 92 days in accordance with the PROCESS CONTROL PROGRAM, or

b. Verification of the existence of a valid contract for SOLIDIFICATION to be performed by a contractor in accordance with a PROCESS CONTROL PROGRAM.

SEQUOYAH - UNIT 2 3/4 11-17

l RADI0 ACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.4 The dose or dose commitment to any member of the public, due to releases of radioactivity from uranium fuel cycle sources, shall be lialted to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months.

APPLICABILITY: At all times.

ACTION:

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifica-ti ons 3. ll . l . 2. a , 3. ll . l . 2. b , 3. l l . 2. 2. a , 3. ll . 2. 2. b , 3.11. 2. 3. a . or 3.ll.2.3.b, in lieu of any other report required by Specification 6. 6.1, prepare and submit a Special Report to the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Specification 3.11.4. This Special Report shall include an analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle scurces (including all effluent pathways and direct radiation) for a 12 consecutive month period that includes the release (s) covered by this report. If the estimated dose (s) exceeds the limits of Specification 3.11.4, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and including the specified information of 6 190.11(b). The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed in other sections of this technical specification.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

t SURVEILLANCE RE0VIREMENTS 4.11.4 Dose Calculations Cumulative dose contributions from liquid and gaseous effluents snall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the 00CM.

SEQUOYAH - UNIT 2 3/4 11-19

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1.

APplICAdILITY: At all ti.aes.

ACTION:

a.

With the radiological environmental monitoring program not being conducted as specified in Table 3.12-1, in lieu of any other report required by Specification 6.9.1 or 6.6.2, prepare and submit to Commission, in the Annual Radiological Operating Report, a description of the reasons for not conductin

, preventing a recurrence, g the program as required and the plans for b.

With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter ,in lieu of any other report required by Specification 6,9.1 or 6.6.1, prepsre and submit

to the Commission within 30 days from the end of the affected calendar quarter a Report pursuant to Specificiation 6.9.1.13.

When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) + concentration (21 + ...g 1.0 limit level (1} limit level (2)

When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

c. With milk or fresh leafy vegetable samples unavailable from one or -

more of the sample locations required by Table 3.12-1, in lieu of any other report required by Specification 6.9.1 or 6.6.1, prepare and submit Ii to the Commission within 30 days, pursuant to Specification 6.9.2, a I Special Report which identifies the cause of the unavailability of samples and identifies locations for obtaining replacement samples.

The locations from which samples were unavailable may then be deleted from those required by Table 3.12-1, provided the locations from which the replacement samples were obtained are added to the environment 31 monitoring program as replacement locations, d.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

A special report pursuant to Specification 6.9.2.

SEQUOYAH - UNIT 2 3/4 12-1

s RADIOLOGICAL ENVIRM#EN] At MONITORING 3/4.12.2 LAND USE CENSUS-LIMIfING C0hDIT,Ipi FOR OPE 9ATION 3.12.2 A latid use census shall be cosidected and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden

of greater than 500 square feet producinq fresh leafy vegetables in each of the 16 meteoro-logical sectors within a distance of five miles. (For elevated releases as defined in Regulatory Guide 1.ill, Revision 1 July 1977, the land use census shall also identify the locations of'411 milk animals and all gardens of greater than 500 square feet prodocing fresh leafy vegetables in each of the 16 meteoro-logical sectors within a distance of three miles.)

AP P L I C A0_I,t.I_T_Y,: *t s all times.

QCTION:

P. With a land use census identifying a location (s) which yields a calcu-lated dosa or dose commitment greater than the maximum value currently being calculated in Specification 4.11.2.3.1, in lieu of any other report iequ(red by specificatiori 6.6.1. , prepara and submit to the Commiss son withi9 30 days af ter.the uodated calculation, pursuant to Specific-at ion 6.9.2, a Special Report which identifies the new location (s).

b. With a land use *:ensus identifying a location (s) which yields a calcu-latm1 dose or doce commitment (via the same exposure pathway) 20 percent greater tnan the highest calculated doce or dose commitment at a location from which samples are currently being obtained in accordance with Speci-fication 3.12.1. in lieu af any other report required by Specifi-cation 6.6.1, prepare anti submit to the Commission within 30 days after the updated calculation, p arsuant to Specification 6.9.2, a Special Report which identifies the new Tocation. The new location shall be added to the rad'ological'environtiental monitoring program within 30 days, it the owner torsents. 1he sampling location, excluding the control st1 tion loca;1on, having the lowest calculated dose or dose commitment (via the sac ekposure pathway) may be deleted from this monitoring program a'ter Oi tober 31 of the year in which this land use census was conducted.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANd REQUIRFEN_T_5 __ -

4.l?.2 The land use unstit shall be conducted at least once per calendar year t'etween the dste of A tril 1 and October 1 using the following techniques:

1. Within a 2-mile t'adius from the plant or within the 15-mrem / year isodose line, whichever.15 larger, enumeration by a door-to-door or equivalent counting technirve. 7 -

2. With a %%e radius frr.<. the plant, en arar . ion by using appropriate technintes wch as roor-to-ioor survay/ mail syevey, telephone survey, serial turvey, or informaticn fr5n local agricultural authorities or other valtiole sources.

Broad leat vegetation sampling ma/ be performed at the site boundary in the direction :,Ntcr with (*ie highesc D/Q in lieu of the garden census.

SEQUOYAd - UNIr 2 , 3/4 12-10 i . 'm K

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ADMINISTRATIVE CONTROLS

d. Review of proposed changes to the Technical Specifications related to radiological assessments involving dose calculations and projections and environmental monitoring.

Authority 6.5.3.7 The RARC shall:

a. Recommend in writing to the Chief, Radiological Hygiene Branch approval or disapproval of ite'ms considered under 6.5.3.6 above.

b. Render determinations in writing with regard to whether or not each item considered under 6.5.3.6 constitutes an unreviewed safety question,

c. Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Director, Nuclear Power Division and the Nuclear Safety Review Board of disagreement between the RARC and the Chief, Radiological Hygiene Branch; hcwever, the Chief, Radiological Hygiene Branch shall have responsibility for resolution of such disagreement pursuant to 6.1.2 above.

Records 6.5.3.8 The RARC shall maintain written minutes of each RARC meeting that at a minimum, document the results of all RARC activities performed under the responsibility and authority provisions of these technical specifications.

Copies shall be provided to the Director, Nuclear Power Division, PORC, and the Nuclear Safety Review Board.

6.6 REPORTA8LE FvrN7 ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a.

The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and

b. Each REPORTABLE EVENT shall be reviewed by the PORC and the results of this review shall be submitted to the NSRB and the Director, Nuclear Power Divison.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The unit shall be placed in at least HOT STANDBY within one hour.

.b. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Director, Nuclear Power Division and the NSR8 shall be notified with 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SEQUOYAH - UNIT 2 6-17

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ACHINISTRATIVE CONTROLS 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to.the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.

STARTup REPORT

6. 9.1.1 ' A summary report of plant start *up and power escalation testing shall

, be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report oces not cover all three events (i.e. , initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

l SEQUOYAH - UNIT 2 6-21

ADMINISTRATIVE CONTROLS The radioactive effluent release report to be submitted "C days after January 1

'of each year shall also include an assessment of radiation doses to the likely most exposed members of the public from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1.

The radioactive effluent release reports shall include the following information for each type of solid waste shipped offsite during the report period:

a. Container volume,

b. Total curie quantity (specify whether determined by measurement.or estimate),

c. Principal radionuclides (specify whether determined by measurement or estimate),

d. Type of waste (e.g. , spent resin, compacted dry waste, evaporator.

. bottoms),

e. Type of container (e.g. , LSA, Type A, Type 8, large Quantity), and

f. SOLIDIFICATION agent (e.g., cement, urea formaldehyde).

The radioactive effluent release reports shall include' unplanned releases from the site to unrestricted areas of radioactive materials in' gaseous and liquid effluents on a quarterly basis.

-Theradioactiveeffluentreleasereportsshalifincludeanychanges.'tothe PROCESS CONTROL PROGRAM (PCP) made during the reporting period.

MONTHLY REACTOR OPERATING REPORT .

~

'6.9.1.10 Routine reports of operating statistics and shutdown experience.1

. including documentation of all ch'allenges to the PORVs or Safety. Valves, shall ~

t

' be submitted on a monthly. basis to the Director, Office of-Management and

-Program Analysis, U.S. Nuclear Regulatory Commission, Washington, 0.C. 20555, j with a. copy to the Regional Office of Inspection and Enforcement, no later l

than the 15th of each month following 'the calendar month covered by .the. report.

[ Any changes' to' the OFFSITE 00SELCALCULATION MANUAL!shall be submitted with 'the

-Monthly Operating Report'within 90 days in.which:the change (s) was made effective.

~

In addition,' a report of any major _ . changes to the radioactive waste treatment

( systems shall be submitted with the Monthly Operating Report for:the period in which the evaluation was' reviewed and accepted by the'PORC.

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SEQUOYAH -UNIT 2 ! 6N4 -

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ADMINISTRATIVE CONTROLS THIS PAGE DELETED SEQUOYAH - UNIT 2 6-25

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ADMINISTRATIVE CONTROLS THIS PAGE DELETED SEQUOYAH - UNIT 2 6-26 1 -:

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.. i ADMINISTRATIVE CONTROLS RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.14 The W(z) function-for normal operation shall be provided to the Direc-tor, Nuclear Reactor Regulation, Attention, Chief of the Core Performance' Branch, U.S. Nuclear Regulatory Commission, Washington,. D.C. 20555 at. least 50 days prior to cycle initial criticality. .In the event that these vclues would be submitted at some other time during. core life, it will be submitted 60 days prior to the'date the values would become effective ~unless otherwise exempted by the Commission.

Any information needed to suport W(z) will be by request from the NRC-and need-not be included in this report.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the. Director of the Office of "

Inspection and Enforcement Regional Office within the time period specified for each report.

.- 6.10 RECORD RETENTION-In addition to the applicable record retention requirements of-Title 10, Code of Federal Regulations,.the following records shall be retained for at least; the minimum period-indicated.

6.10.1 The following records'shall be retained-for at least five' years:

- a. . Records and ' logs of unit operation covering time interval at each -

power level.

b. Records'and logs of principal maintenance activities, inspections, repair and replacement of principal items of. equipment related to nuclear safety.-

SEQUOYAH - UNIT 2 6-57

l 5 .

3 ADMINISTRATIVE CONTROLS 6.10.1 (continued)

c. All REPORTABLE EVENTS submitted to the Commission.

d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

e. Records of changes made to the procedures required by Specification 6.8.1 and 6.8.4.

f. Records of radioactive shipments.

g. Records of sealed source and fission detector leak tests and results.

h. Records of annual physical inventory of all scaled source material of record.

6.10.2 The following records shall be retained for the duration of the Unit Operating License:

a. Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report.

b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories,

c. Records of radiation exposure for all individuals entering radiation control areas.

d. Records of gaseous and liquid radioactive material released to the environs.

c. Records of transient or operational cycles for those unit components identified in Table 5.7-1.

f. Records of reactor tests and experiments. .

g. Records of training and qualification for current members of the unit staff,

h. Records of in-service inspections performed pursuant to these Technical Specifications.

i. Records of Quality Assurance activities required by the Operational Quality Assurance Manual,

j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k. Records of meetings of the PORC, RARC, and the NSRB.

1. Records of analyses required by the radiological environmental monitoring program.

^

SEQUOYAH - UNIT 2 6-28

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REACTOR COOLANT SYSTEM

! - BASES 3/4.4.5 STEAM GENERATORS i

! The Surveillance Requirements for~ inspection of the steam generator tubes

ensure that the structural integrity of this portion of the RCS will be maintained.

The program for inservice inspecti,on of steam generator tubes is based on a modification of Regulatory Guide 1.83, llevision 1. Inservice inspection of ;

j steam generator tubing is essential in order to maintain surveillance of the

conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due tn design, manufacturing errors, or inservice conditions that lead to corrosion. Inservice inspection of steam i generator tubing also provides a means of characterizing the nature and cause j of any tube degradation so that corrective measures can be taken.

The plant is expected to be operated in a manner such that the secondary coolant will be maintained within those chemistry limits found to~ result ~ in negligible corrosion of the steam generator tubes. If the secondary coolant chemistry is not maintained within these limits, localized corrosion may

likely ' result in stress corrosion cracking. The extent of cracking during I

plant operation would be limited by the limitation of steam generator tube i leakage between the primary coolant system and the secondary coolant system j (primary-to-secondary leakage = 500 gallons per day per steam generator).

Cracks having a primary-to-secondary leakage-less than this limit during j operation will have an adequate margin of safety.to withstand the loads.

imposed during normal operation and by postulated accidents. Operating plants i have demonstrated that primary-to-secondary leakage of 500 gallons per day per l steam generator can readily be detected by radiation monitors of steam generator blowdown. Leakage in excess of this limit will require plant shutdown and an.

unscheduled inspection, during which the leaking tubes wfil be located and

! plugged.

! Wastage-type defects are unlikely with proper chemistry treatment'of the j secondary coolant. However, even if a defect should develop in service, it

will be found during scheduled inservice steam generator tube' examinations.

Plugging will be required for all tubes with imperfections exceeding the l . plugging limit of 40% of the tube nominal wall thickness. Steam generator i tube inspections of' operating plants have demonstrated the capability to

, reliably detect degradation that has penetrated 20% of the originc1 tube wall i thickness.

j . . .

{

~

Whenever the results of a.1y steam generator tubing inservice intjection fall into Category C-3, these results will be promptly reported to the Commission pursuant to Specification 6.6.1 prior to resumption of plant operation. Such cases will be considered by the Commission on a case-by-case basis and say.

! result in a requirement for analysis, laboratory 'xaminations, e tests, additional-

j. eddy-current inspection, and revision of the Technical Specifications, if necessary.

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SEQUOYAH'- UNIT 2 B 3/4 4-3 i.

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4 ENCLOSURE 2 JUSTIFICATION FOR PROPOSED TECHNICAL SPECIFICATION CHANGES SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2-f The proposed technical specification changes are being submitted as -

required' by 10 CFR 50.73, which specifies the new reporting require-ments for licensee event. reports. These new changes were also requested by the December 19,:1983 letter from D. G. Eisenhut to "All Licensees. . . ."

These changes are administrative changes only and have no affect on plant safety. In accordance with 10 CFR 50.92, attached is the significant hazards consideration determination which states that no significant hazards are involved.

4 i

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. ATTACHMENT SIGNIFICANT HAZARDS CONSIDERATIONS -

v.

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1. Is the probability of an occurrence, or are the consequences of an accident previously evaluated in the safety analysis report, significantly increased?

No. This change modifies reporting requirements to conform to .

NUREG-1022 standards. No facet of plant operation is affected.

1

2. Is the possibility for an accident of a new or different type Chan evaluated previously in dhe safety analysis report created?

No. No change has been made to plant equipment or operation. This is an administrative change only and does not create any new type of accident.

3 Is the margin of safety significantly reduced?

No. Changes to reporting requirements will.not have any impact on -

safety margins.

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ML20083R331

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